Results 151 to 160 of about 1,865 (177)
Some of the next articles are maybe not open access.
Foreword: Special Issue on the RELAP5-3D Computer Code
Nuclear Science and Engineering, 2016(2016). Foreword: Special Issue on the RELAP5-3D Computer Code. Nuclear Science and Engineering: Vol. 182, No. 1, pp. iii-iii.
openaire +1 more source
Research on the steam–gas pressurizer model with Relap5 code
Nuclear Science and Techniques, 2017Steam–gas pressurizers are self-pressurizing, and since steam and noncondensable gas are used to sustain their pressure, they experience very complicated thermal–hydraulic phenomena owing to the presence of the latter. A steam–gas pressurizer model was developed using Relap5 code to investigate such a pressurizer’s thermal–hydraulic characteristics ...
Xi-Zhen Ma, Hai-Jun Jia, Yang Liu
openaire +1 more source
Multi-component diffusion analysis and assessment of GAMMA code and improved RELAP5 code
Nuclear Engineering and Design, 2007Abstract A loss-of-coolant accident (LOCA) has been considered a critical event for very high temperature gas-cooled reactor (VHTR). Following helium depressurization, it is anticipated that unless countermeasures are taken, air will enter the core through the break by molecular diffusion and ultimately by natural convection leading to oxidation of ...
No, HC No, Hee Cheon +5 more
openaire +2 more sources
Research of complete loss of flow accident for AP1000 based on RELAP5 code
Journal of Computational Methods in Sciences and Engineering, 2015AP1000 reactor is the typical ``third-generation'' nuclear power plant in the world at present. The primary system of AP1000 nuclear power plant was modeled using RELAP5/MOD 3.3 code, and the transient thermal hydraulic characteristics were analyzed under complete loss of flow accident (CLOFA).
Jianping Jing +3 more
openaire +1 more source
BWR transient analysis with the coupled code system S3K/RELAP5
Kerntechnik, 2011Abstract This paper describes the coupled code system S3K-RELAP5 and the application of the code system to BWR transients without scram. In addition short descriptions are given for application of the coupled system to fast transients and rod drop accidents. The models and methods of the code system are presented.
C. Jönsson +3 more
openaire +1 more source
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code
2000SPES is an experimental facility which allows the assessment of thermalhydraulic codes through the simulation of a wide range of physical phenomena characterising different accident scenarios in PWRs. In 1999, in view of a possible proposal for an international cooperative programme, ENEA provided the SIET company with limited funding to restore the ...
D'AURIA, FRANCESCO SAVERIO +5 more
openaire +2 more sources
QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code
2008The QUENCH program is a research program running at Karlsruhe Research Center (FZK – Forschungszentrum Karlsruhe) that is focused on the investigation of cladding behaviour and hydrogen source term following the water injection in the uncovered core of a light water reactor (LWR).
Šadek, Siniša +2 more
openaire +1 more source
RELAP5/Mod3.2 - Quabox/Cubbox-Hyca Coupled Code
1997QUABOX/CUBBOX-HYCA is well known 3D coarse mesh neutron kinetics code developed in GRS Garching. It is coupled to different code systems and used for calculation of different types of reactors. Objective of this work is to develop code, based on RELAP5/mod3.2 and QUABOX/CUBBOX-HYCA, for class of transients characterized by spatial dependence in the ...
Grgić, Davor +6 more
openaire +2 more sources
Croatian Experience in the Use of Coupled 3D Code With RELAP5
1999N ...
Grgić, Davor, Bajs, Tomislav
openaire